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    Iron–Chromium–Aluminum (FeCrAl) Cladding Oxidation Kinetics and Auxiliary Feedwater Sensitivity Analysis—Short-Term Station Blackout Simulation of Surry Nuclear Power Plant 

    Source: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 004:;page 41002
    Author(s): Wang, Jun; Mccabe, Mckinleigh; Christopher Haskin, Troy; Wu, Yingwei; Su, Guanghui; Corradini, Michael L.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Accident tolerant fuels (ATF) and steam generator (SG) auxiliary feedwater (AFW) extended operation are two important methods to increase the coping time for nuclear power plant safety response. In light of recent efforts ...
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    The Development of Candling Module Code in Module In vessel Degraded Analysis Code MIDAC and the Relevant Calculation for CPR1000 During Large Break LOCA 

    Source: Journal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 002:;page 21002
    Author(s): Wang, Jun; Fan, Yuqiao; Zhang, Yapei; Ni, Xinghe; Tian, Wenxi; Corradini, Michael L.; Su, Guanghui; Qiu, Suizheng
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The occurrence of Fukushima has increased the focus on the development of severe accident codes and their applications. As a part of Chinese “National Major Projects,â€‌ a module invessel degraded analysis code (MIDAC) ...
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